Effect of pressure and flow on the BWR rod drop accident
Conference
·
OSTI ID:5761557
This paper has calculated the pressure rise and inlet flow variation during a rod drop accident. Results show that the effect of these parameters tends to increase the calculated peak fuel enthalpy. Nevertheless, it is clear that the moderator feedback still has a strong inherent mitigating effect on the transient, and the effect of pressure and flow on the RDA is, in this sense, of second order.
- Research Organization:
- Brookhaven National Lab., Upton, NY (USA)
- Sponsoring Organization:
- USDOE; Nuclear Regulatory Commission
- DOE Contract Number:
- AC02-76CH00016
- OSTI ID:
- 5761557
- Report Number(s):
- BNL-NUREG--28999; CONF-810606--110; ON: TI85004758
- Country of Publication:
- United States
- Language:
- English
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·
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
FEEDBACK
FLUID FLOW
PRESSURIZING
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTORS
ROD DROP ACCIDENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
BWR TYPE REACTORS
FEEDBACK
FLUID FLOW
PRESSURIZING
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTORS
ROD DROP ACCIDENTS
WATER COOLED REACTORS
WATER MODERATED REACTORS